ML18153B982
| ML18153B982 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/09/1989 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 89-791, NUDOCS 8911210314 | |
| Download: ML18153B982 (2) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 9, ~~QV /j A 9: Q9 Mr. Stewart D. Ebneter Regional Administrator
- United States Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323
Dear *Mr. Ebneter:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 DISCRETIONARY ENFORCEMENT PRESSURIZER SAFETY VALVE OPERABILITY Serial No.
- 89-791 NURPC Docket No.
50-281 License No.
DPR-32 Technical Specific.ation 3.1.A.3.a. requires that "One valve shall be operable
- whenever the head is on the reactor vessel, except during hydrostatic tests." To allow for simultaneous testing of the three pressurizer safety valves to avoid an adverse impact on Unit 2 restart, discretio.nary enforcement has been requested.
As. discussed in a telephone conversation with your staff on November 9,
- 1989, Virginia Electric and Power Company was granted discretionary enforcement for a period of ten days (through November 19, 1989) to provide for the simultaneous removal of the three pressurizer safety valves.
This request was made due to the recent pressurizer safety valve lift during the RCS overpressure test while returning the unit to service. Based on this event, we have decided to test and reset the three Unit 2 valves.-
Unit 2 is presently in cold shutdown. Our technical justification for this request is as follows:
(1)
The
- bases of Technical Specification 3.1.A.3.a
- is to prevent overpressurization events whenever. RCS integrity is maintained.
Removal of the safety valves provides an equivalent relief path to prevent any overpressurization event.
(2)
The foreign material exclusion cover has been previously analyzed in terms of its impact on relief capacity. This analysis determined that -such exclusion covers do not adversely impact the relief capacity of.the vacant valve sites.
8911210314 OQ110 9 fDR ADOCK 5§oo6i81 p
(3) -*
Furthermore, AHR relief and PORV capacity provides additional protection from over_pressurization.
We conclude that removal of the safety valves and use of the vacant valve site with
.foreign material exclusion covers provides the equivalent overpressurization protection as -an operable safety valve.
Should -YOU have any further questions or require any additional information, please contact us.
ft:(ttfo W. L. Stewart bL-Senior Vice President - Nuclear -
cc:
U. S. Nuclear Regulatory Commission Attention: Docurnent Control Desk Washington, D. C. 20555 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station